ML20149K862

Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review

ML20149K862
Person / Time
Site:	Rancho Seco
Issue date:	02/12/1988
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
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ML20149K855	List: ML20149K852 ML20149K862
References
NUDOCS 8802240015
Download: ML20149K862 (1)

Text

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 138-HEMBERSHIP 6.5.1.3 Membership of the PRC shall be as defined below:

s a.

A list of members made up of personnel filling positions shown in the Nuclear Organization (Fig. 6.2-2) and others who meet or exceed the minimum qualifications of ANSI N18.1-1971 shall be developed and approved by the AGM, Nuclear Power Production.

b.

A list of alternate members of the PRC shall be developed and approved by the AGM, Nuclear Power Production.

c.

The Chairman of the PRC shall be appointed by the AGH, Nuclear Power Production. When a meeting is scheduled or an emergency meeting is necessary, and the PRC Chairman will be absent, an alternate Chairman may be designated by the PRC Chairman or the AGM, Nuclear Power Production from among the PRC members described in Specification 6.5.1.2.

HEETING FREOUENCY 138-6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman, or as directed by the AGH, Nuclear Power Production.

OUORUM 138-6.5.1.5 A Quorum of the PRC shall consist of a majority of the members listed in Specification 6.5.1.2 including the Chairman or alternate Chairman. No more than two alternates shall participate in PRC activities at any one time for the purpose of establishing a quorum.

RESPONSIBILITIES 138-6.5.1.6 The Plant Review Committee shall be responsible for review of:

a.

The required safety evaluation of 1) all procedures required by Specification 6.8 and changes thereto, and 2) any other proposed procedures or changes thereto which are as determined by the AGM, Nuclear Power Production to affect nuclear safety.

138-~

b.

The safety evaluations of all proposed tests and experiments that affect nuclear safety.

c.

All proposed changes to the Technical Specifications or the Operating License.

138-d.

All safety evaluations of proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Items which are determined by a qualified reviewer as not involving an unreviewed safety question, a change of technical specifications, or a change in a licensing basis document, need not be reviewed by the PRC.

138-e.

Investigations of all violations of the Technical Specifications to determine adequacy of corrective action and to detect any degrading trend, f.

Facility operations to detect potential safety hazards.

l$g22ggg ggg Proposed Amendment No. 138, Rev. 2. Supp. 4 6-4 g

P DCD

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